ML16138A593
| ML16138A593 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/08/1987 |
| From: | Youngblood B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML16138A594 | List: |
| References | |
| NUDOCS 8706120315 | |
| Download: ML16138A593 (8) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION in WASHINGTON, D. C. 20555 DUKE POWFR COMPANY DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.159 License No. DPR-38
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application.for amendment to the Oconee Nuclear Station, Unit 1 (the facility) Facility Operating License No. DPR-38 filed by the Duke Power Company (the licensee) dated February 10, 1986, as supplemented on August 20, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter 1; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter 1; D. The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations, and all applicable requirements have been satisfied.
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachments to this license amendment, and Paragraph 3.B of Facility Operating License No. DPR-38 is hereby amended to read as follows:
3.B Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 159, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
8706120315 870608 PDR ADOCK 05000269 P
-2
- 3. This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION B.J. Youngblood, Director Project Directorate 11-3 Division of Reactor Projects -
I/IT
Attachment:
Technical Specification Changes Date of Issuance:
June 8, 1987 PDI -3 DRP-I/I1 3/DRP-I/II the a
PDII /P-/11 MWa/rad P4i 7 B4JyYo8ngblood 0 4/2/87 0 4 1,/8 7 04A/V87 02/87
oUNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 159 License No. DPR-47
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the Oconee Nuclear Station, Unit 2 (the facility) Facility Operating License No. DPP-47 filed by the Duke Power Company (the licensee) dated February 10, 1986, as supplemented on August 20, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter 1; D. The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's reaulations, and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachments to this license amendment, and Paragraph 3.8 of Facility Operating License No. DPR-47 is hereby amended to read as follows:
3.8 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.159, are hereby incorporated in the license. The licensee shall operate the facility in accordance with-the Technical Specifications.
-2
- 3. This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION B.J. Youngblood, Director Project Directorate 11-3 Division of Reactor Projects -
I/II
Attachment:
Technical Specification Changes Date of Issuance: June 8, 1987 PD I-3RP-I/II P
3/DRP-I/II a
PDI P-I/1 MD an/rad H 's 7BJJ gblood 04//8 04 87 87 7
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pEIt UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO.
50-287 OCONEE NUCLEAP STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 156 License No. DPR-55
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the Oconee Nuclear Station, Unit 3 (the facility) Facility Operating License No. DPR-55 filed by the Duke Power Company (the licensee) dated February 10, 1986, as supplemented on August 20, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission s rules and regulations set forth in 10 CFR Chapter 1; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter 1; D. The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 5k of the Commission's regulations, and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachments to this license amendment, and Paragraph 3.B of Facility Operating License No. DPR-55 is hereby amended to read as follows:
3.B Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 156, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
-2
- 3. This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION B.J. Youngblood, Director Project Directorate 11-3 Division of Reactor Projects -
I/II
Attachment:
Technical Specification Changes Date of Issuance: June 8, 1987 PDI -3DRP-I/II P
/DRP-I/1I e da PDH-3/DRP-I/II MWna
-/rad B I B ungblood 04/87 4,V87
- 0.
87 OA/ rh87
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 159 TO DPR-38 AMENDMENT NO. 159 TO DPR-47 AMENDMENT NO. 156 TO DPR-55 DOCKET NOS. 50-269, 50-270, AND 50-287 Replace the following page of the Appendix "A" Technical Specifications with the attached page. The revised page is identified by amendment number and contains a vertical line indicating the area of change.
Remove Insert Page Page 3.1-24 3.1-24
3.1.12 Reactor Coolant System Subcooling Margin Monitor Specification 3.1.12.1
- a.
A minimum of two of the three Reactor Coolant System subcooling monitors (Loop "A" temperature, Loop "B" temperature, and Core temperature) shall be operable when the average RCS coolant temperature is above 300'F.
- b.
If only one monitor is operable, at least one other monitor shall be restored to operable status within seven days or the unit shall be in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
C.
If all of the subcooling monitors are inoperable, then restore at least one monitor to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Bases The operability requirements of the Reactor Coolant System subcooling margin monitors ensures that sufficient information is available to the operators to provide prompt recognition of saturated conditions in the primary coolant system and advanced warning of the approach to inadequate core cooling.
Guidance for these requirements was provided by the NRC letter of July 2, 1980, and derived from the implementation of the TMI-2 lessons learned program.
OCONEE -
UNITS 1, 2, & #
3.1-24 Amendment No. 159 (Unit 1)
Amendment No. 159 4Unit 2)
Amendment No. 156 (Unit 3)